Numerical study of tritium transport characteristics in Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF)

被引:9
|
作者
Wang, Chenglong [1 ,2 ]
Qin, Hao [1 ,2 ]
Zhang, Dalin [1 ,2 ]
Tian, Wenxi [1 ,2 ]
Qiu, Suizheng [1 ,2 ]
Su, G. H. [1 ,2 ]
机构
[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Shaanxi, Peoples R China
[2] Xi An Jiao Tong Univ, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian, Shaanxi, Peoples R China
基金
中国博士后科学基金; 高等学校博士学科点专项科研基金;
关键词
D O I
10.1016/j.nucengdes.2018.06.013
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Tritium control is one of the most key issues for the development of Molten Salt Reactor (MSR). The tritium transport characteristics in 2MWth Thorium Molten Salt Reactor-Solid Fuel (TMSR-SF) proposed by Shanghai INstitute of Applied Physics (SINAP) is studied in this paper. Three works are conducted: Firstly, an integrated numerical model is established, including tritium production, adsorption, diffusion, corrosion and permeation. Secondly, the Tritium trAnsPort chAracteristics analysiS code (TAPAS) for TMSR-SF is developed and benchmarked. The results prove the fidelity and accuracy of TAPAS. Finally, the distributions of the key variables including TF, T-2 and Cr2+ in TMSR-SF system at both steady and transient state are obtained. In addition, some methods for tritium mitigation are evaluated by TAPAS. Numerical results show that tritium can be efficiently removed from the molten salt via graphite absorption. The amount of T-2 at steady state is two orders of magnitude more than TF. Tritium permeation can be prevented by increasing Li-7 enrichment and reducing redox potential. Tungsten or similar low-permeability material is a candidate for tritium barrier when covered on the surface of the heat exchanger wall. This work provides some valuable considerations for the tritium control in the MSR.
引用
收藏
页码:391 / 399
页数:9
相关论文
共 50 条
  • [21] Core neutronic characterization of a large molten-salt cooled thorium-based solid fuel fast reactor
    Peng, Yu
    Zhu, Guifeng
    Zou, Yang
    Liu, Sijia
    Xu, Hongjie
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020, 44 (10) : 8062 - 8073
  • [22] Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes
    Yu, Chenggang
    Wu, Jianhui
    Zou, Chunyan
    Cai, Xiangzhou
    Ma, Yuwen
    Chen, Jingen
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 43 (08) : 3628 - 3639
  • [23] Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
    Ashraf, O.
    Rykhlevskii, Andrei
    Tikhomirov, G. V.
    Huff, Kathryn D.
    ANNALS OF NUCLEAR ENERGY, 2020, 137
  • [24] Fuel depletion study of the molten salt demonstration reactor
    Creasman, Sarah Elizabeth
    Harrison, T. Jay
    Heilbronn, Lawrence H.
    NUCLEAR ENGINEERING AND DESIGN, 2024, 418
  • [25] Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
    Ashraf, O.
    Rykhlevskii, Andrei
    Tikhomirov, G.V.
    Huff, Kathryn D.
    Annals of Nuclear Energy, 2020, 137
  • [26] Parametric Study of Natural Circulation Flow in Molten Salt Fuel in Molten Salt Reactor
    Pauzi, Anas Muhamad
    Cioncolini, Andrea
    Iacovides, Hector
    ADVANCING OF NUCLEAR SCIENCE AND ENERGY FOR NATIONAL DEVELOPMENT, 2015, 1659
  • [27] BREEDING PROPERTIES STUDY ON HIGH POWER THORIUM MOLTEN SALT REACTOR
    Liu, Yafen
    Guo, Rui
    Cai, Xiangzhou
    Yan, Rui
    Zou, Yang
    Zhou, Bo
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5, 2017,
  • [28] Numerical Analysis of Tritium Transport Characteristics in Fluoride-salt-cooled High-temperature Reactor
    Qin H.
    Wang C.
    Zhang D.
    Tian W.
    Qiu S.
    Su G.
    Wang, Chenglong (clwang@mail.xjtu.edu.cn), 2018, Atomic Energy Press (52): : 434 - 440
  • [29] Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
    Ashraf, O.
    Rykhlevskii, Andrei
    Tikhomirov, G.V.
    Huff, Kathryn D.
    Annals of Nuclear Energy, 2021, 152
  • [30] Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel
    Liu, Limin
    Zhang, Dalin
    Lu, Qing
    Wang, Kunpeng
    Qiu, Suizheng
    PROGRESS IN NUCLEAR ENERGY, 2016, 86 : 1 - 10